Improved Dose Estimates for Nuclear Criticality Accidents-Reference-Cited by-同舟云学术

Improved Dose Estimates for Nuclear Criticality Accidents

Published:1995-08 Issue:2 Volume:111 Page:227-240
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Wilkinson Alan D.¹,Basoglu B.¹,Bentley C. L.¹,Dunn M. E.¹,Haught Chris F.²,Plaster M. J.¹,Yamamoto T.³,Dodds H. L.⁴,Hopper Calvin M.⁵

Affiliation:

1. University of Tennessee, Nuclear Engineering Department Knoxville, Tennessee 37996-2300

2. Martin Marietta Utility Systems Building X-1000, MS 5023, Piketon, Ohio 45661

3. Japan Atomic Energy Research Institute Tokai Research Establishment, Tokai-mura, Naka-gun, Ibaraki-ken 319-11, Japan

4. University of Tennessee, Nuclear Engineering Department Knoxville, Tennessee 3 7996-2300

5. Martin Marietta Energy Systems Oak Ridge National Laboratory, P.O. Box 2008, Building 6011 MS 6370, Oak Ridge, Tennessee 37831-6370

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.13182/NT95-A35132

Reference11 articles.

1. CM. HOPPER, “Slide Rule for Estimating Nuclear Criticality Information,” Y-DD-145, Union Carbide, Oak Ridge National Laboratory (1974).

2. The Rate of Decay of Fission Products

3. J. K. WARKENTIN, “Gamma Energy Release from Fission Product Decay Following a Short Reactor Transient,” TID-4500, Phillips Petroleum Company (Apr. 1966).

4. D. E. HANKINS, “A Study of Selected Criticality-Dosimetry Methods,” LA-3910, Los Alamos Scientific Laboratory (1968 June).

5. “SASI—A One-Dimensional Shielding Analysis Module SCALE —A Modular Code System for Performing Standardized Computer Analysis for Licensing Evaluation,” NUREG/CR-0200, Rev. 4 (ORNL/NUREG/CSD-2/R4), Vol.I, Sec. SI Oak Ridge National Laboratory (draft Feb. 1990).